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Development of High-Temperature Strain Gages

Description: From Introduction: "An improved high-temperature gage was needed, and in an attempt to fill this need an investigation was initiated in February 1954 in the Enameled Metals Laboratory at the National Bureau of Standards. The present Monograph constitutes a final summary on this program."
Date: March 17, 1961
Creator: Pitts, J. W. & Moore, D. G.
Partner: UNT Libraries Government Documents Department
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Aeroradioactivity Survey and Areal Geology of the Oak Ridge National Laboratory Area, Tennessee and Kentucky (ARMS-I)

Description: Report regarding an airborne radioactivity survey that took place over a 10,000 square mile area around the Oak Ridge National Laboratory near Knoxville, Tennesse. Topics include the types of bedrock noted in the area as well as their levels of radioactivity.
Date: March 1961
Creator: Bates, Robert G.
Partner: UNT Libraries Government Documents Department
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Preliminary Design of a Basic Radiation Effects Reactor (BRER)

Description: From Introduction: "Information has been accumulated about the property changes produced, but there are essentially no reliable quantitative data correlating property changes with the magnitude and energy distribution of the neutron fluxes responsible for the changes. The design of the Basic Radiation Effects Reactor (BRER) presented herein stems from the two main requirements: 1. a fairly high-level, high-energy neutron flux with minimal thermal neutron and gamma-ray background is desired; 2. … more
Date: March 1961
Creator: MacFarlane, D. R.; Rohde, R. R.; Toppel, B.; Charak, I. & Unger, H.
Partner: UNT Libraries Government Documents Department
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A Report on Some Attempts to Cast Centrifugally Fuel Elements of Small Diameter

Description: Report issued by the Argonne national Laboratory discussing centrifugal casting of thin uranium plates. The applicability of the centrifugal casting technique to the production of multiple castings of fuel pins of small diameter and of thin fuel plates was investigated. This report includes tables, illustrations, and photographs.
Date: March 1961
Creator: Yaggee, F. L.
Partner: UNT Libraries Government Documents Department
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The Cold Pressing of Sinterable UO₂

Description: The intent of this work was to explore more fully the pressing of sinterable UO2 powders into cylindrical compacts in the hope that a more precise prediction of green density in terms of powder properties, pressure, and geometry could be evolved.
Date: March 27, 1961
Creator: Levey, R. P., Jr.
Partner: UNT Libraries Government Documents Department
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Final Design Report: DR-1 Gas Loop

Description: Report describing the performance, fission product tolerance, design, and costs of the DR-1 Gas Loop, which is an in-reactor test facility.
Date: March 1961
Creator: Baars, R. E.
Partner: UNT Libraries Government Documents Department
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THE EIGHTFOLD WAY: A THEORY OF STRONG INTERACTION SYMMETRY

Description: A new model of the higher symmetry of elementary particles is introduced ln which the eight known baryons are treated as a supermultiplet, degenerate in the limit of unitary symmetry but split into isotopic spin multiplets by a symmetry-breaking term. The symmetry violation is sscribed phenomenologically to the mass differences. The baryons correspond to an eight-dimensional irreducible representation of the unitary group. The pion and K meson fit into a similar set of eight particles along wit… more
Date: March 15, 1961
Creator: Gell-Mann, M.
Partner: UNT Libraries Government Documents Department
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Quarterly Status Report on LAMPRE Program for Period Ending February 20, 1961

Description: S>The LAMPRE-I project is summarized in terms of capsule development and production, sodium system, cover gas system, capsule charge, shielding, and fuel storage facility. The loading of the LAMPRE-I core was begun on January 20, 1961 with the sodium temperature set at 160 deg C. The reactor was brought to criticality on February 17, 1961. Operation of the Sodium Test Facility was continuous ex cept for 6 maintenance and inspection shutdowns resulting in 680 idle hours. The intermediate sodium … more
Date: March 1, 1961
Partner: UNT Libraries Government Documents Department
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HYDRAULIC TESTS OF A PROTOTYPE HALLAM FUEL ELEMENT (SU-9) TO BE TESTED IN SRE

Description: Pressure-drop measurements were made across a mockup of a Hallam prototype fuel element in a test section installed in the Hallam Hydraulic Loop. The flow channel was identical to an SRE fuel channel and included simulated upper and lower plenums. The fuel element mockup was equipped with a Hallam-type variable orifice at the channel exit and a fixed orifice in the strainer basket at the bottom of the element. Tests were performed to determine the optimum size for the fixed orifice and the temp… more
Date: March 13, 1961
Creator: Beeley, R. J.
Partner: UNT Libraries Government Documents Department
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OPERATIONAL INVESTIGATION OF NUCLEAR INSTRUMENTATION. Test Results T- 643725. Section 1

Description: A test was run to determine the capability of the nuclear instrumentation system to indicate reactor transient behavior and to test the linearity and alignment of all four channels. The response to a resctivity insertion was found to be linear in the range tested 5 x 10>s-/sup >> / 5 x 10>s-/ sup > /p Channel A showed the best aligmnent. (D. L.C.)
Date: March 20, 1961
Partner: UNT Libraries Government Documents Department
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REACTOR VESSEL BELLOWS

Description: Two types of bellows configurations were proposed for the HNPF Reactor Vessel. It was established that the only logical manner of comparing the two designs is on an actual stress basis which implies equal life for each bellows. Results are presented giving the minimum number of convolutions required for each design. (auth)
Date: March 1, 1961
Creator: Susnir, J.
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report

Description: Research and development activities are reported on EBWR, BORAX-V, ZPR- III, ZPR-VI, ZPR-IX, EBR-I, and EBR-II. Thermal- and fast-reactor safety studies are summarized. Applied nuclear and reactor physics, reactor fuels development, reactor materials development, reactor components development, heat engineering, separations processes, and advanced reactor development are discussed. (M.C.G.)
Date: March 1, 1961
Partner: UNT Libraries Government Documents Department
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Valve Operating System Performance Test. Core 1, Seed 2. Test Results T- 641114

Description: A test was run on the Shippingport Pressurized Water Reactor on June 15, 1960, to determine whether or not the pressure snd water flask volume of the valve operating system are sufficient to meet requirements under both normal and emergency conditions. The system was found to be satisfactory. A two-hour leak test indicated leakage. (D.L.C.)
Date: March 14, 1961
Partner: UNT Libraries Government Documents Department
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REVIEW OF INVESTIGATIONS PERTINENT TO THE PREDICTION OF THE THERMAL BEHAVIOR OF FAST REACTORS UNDER ABNORMAL OPERATING CONDITIONS

Description: Results are summarized for a survey of methods for predicting fuel element and coolant behavior in sodiumcooled fast reactors under abnormal operating conditions. Circumstances prior to, during, and after meltdown are considered, and the behavior of fuel and coolant during transients is discussed. Reactor excursions, theory of fuel element thermal transients, reactor coolant transients in single and two-phase flows, and specific topics such as two-phase flow patterns, two-phase pressure drop, a… more
Date: March 15, 1961
Creator: Beers, F.E.
Partner: UNT Libraries Government Documents Department
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